Pages that link to "NRCOC"
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The following pages link to NRCOC:
Displayed 50 items.
- ML033230387 (← links)
- NL-03-1661, Transmittal of Edwin I. Hatch Revised Emergency Plan Implementing Procedures 73EP-EIP-054-0, Version 6.0 & 73EP-EIP-073-0, Version 15.2 (← links)
- ML031970735 (← links)
- ML031400023 (← links)
- NL-03-0939, Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1 (← links)
- L-2003-094, Emergency Plan and Implementing Procedure Changes (← links)
- L-2003-072, Emergency Plan Implementing Procedures, Table of Contents - HP 203.4 (← links)
- ML030840740 (← links)
- NL-03-0322, Emergency Implementing Procedure Revisions (← links)
- ML023610154 (← links)
- ML023370397 (← links)
- ML022830536 (← links)
- L-2002-145, Emergency Plan Implementing Procedure, Rev. 7 to EPIP-13 and Rev. 41 to HP-90 (← links)
- NLS2002091, Emergency Plan Implementing Procedures (← links)
- L-2002-105, Emergency Plan Implementing Procedure Changes (← links)
- L-2002-074, Emergency Plan Implementing Procedure Changes (← links)
- L-2002-083, Emergency Plan Implementing Procedure (← links)
- ML021150741 (← links)
- ML020920084 (← links)
- ML020850757 (← links)
- ML020660602 (← links)
- ML020600071 (← links)
- ML20084L988 (← links)
- ML20078L653 (← links)
- ML20078J110 (← links)
- ML20101E385 (← links)
- ML20138Q845 (← links)
- ML20195J308 (← links)
- ML20195E614 (← links)
- ML20203K827 (← links)
- ML20196J907 (← links)
- ML20217N317 (← links)
- ENS 55574 (← links)
- ML20210N557 (← links)
- ML20210L332 (← links)
- ENS 55831 (← links)
- 05000250/LER-2021-004, Cancelation of LER 2021-004, Through-Wall Leakage from Core Exit Thermocouple Tubing (← links)
- L-84-240, Forwards Written Responses & Ref Matls to Substantiate Statements Made During 840907 Exit Interview Re Reactor & Senior Reactor Operating Exams on 840905 (← links)
- NRC-23-0037, 56542-EN 56542 - Fermi (← links)
- 05000251/LER-1985-008-01, :on 850411,small Leak Discovered at Fitting on Test Connection Between Containment & Containment Isolation Valve.Caused by Test Connection Leakage & Malfunction of Valve CV-4-951 (← links)
- 05000250/LER-1985-010, :on 850330,subcooling Margin Monitors Considered Inoperable Per Tech Specs & Plant Shutdown.Caused by Failure of RCS Temp Elements to Meet Environ Acceptance Criteria.Elements Will Be Replaced (← links)
- 05000250/LER-1984-033, :on 841213,reactor Trip Occurred Due to Generator Trip & Subsequent Turbine Trip.Caused by Fault in Exciter Created by Shorting of Dc to Ac Side of Rotor. Exciter Rotor Replaced (← links)
- 05000251/LER-1985-005, :on 850207,spurious Safety Injection Signal Generated in ESF Sys W/No Resultant Safety Injection Flow. Caused by Blown Fuse on Flow Comparator of Steam Generator B Coincident W/Electrical Spike.Fuse Replaced (← links)
- 05000251/LER-1985-006-01, :on 850207,auxiliary Feedwater Sys Actuated Automatically.Caused by Incorrect Setting of Relay on 4,160- Volt Bus C.Auxiliary Feedwater Pumps Reset & Affected Relay Rewired (← links)
- 05000251/LER-1984-027-01, :on 841130,RHR Sys Flow Interrupted for 4 Minutes.Caused by Closure of Isolation Valve MOV-4-751 in RHR Pump Suction Line Due to Malfunction in Pressure Controller PC-405B.RHR Pump B Restarted (← links)
- 05000251/LER-1985-003-01, :on 850206,reactor Tripped Due to Reactor Protection Logic of Steam Flow Greater than Feed Flow.Caused by Steam Flow/Feed Mismatch Alarm & Decrease in Steam Generator Level (← links)
- 05000251/LER-1984-026-01, :on 841124,automatic Initiation of Auxiliary Feedwater Sys Occurred.Caused by Personnel Oversight by Not Maintaining Adequate Level in Steam Generator B.Auxiliary Feedwater Pumps Stopped & Secured (← links)
- 05000251/LER-1984-025-01, :on 841124,reactor Trip Occurred.Caused by Ground in One Stab Connector of Reactor Coolant Pump 4a Breaker.Unit Brought to Refueling Shutdown Condition to Deenergized 4a 4-kV Bus for Insp & Repair (← links)
- 05000250/LER-1984-029, :on 841127,turbine Runback to 50 MW & Approx 65% Reactor Power Occurred.Caused by Personnel Error.Load Decrease Stopped by Raising Governor Oil Pressure Which Increased Generator Load to Approx 225 MW (← links)
- 05000250/LER-1984-025, :on 840923,evaluation on Intake CWS Revealed Component CWS HXs May Not Meet Design Heat Removal Capability Under Design Inlet Condition.Temporary Limiting Condition for Operation Established (← links)